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Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20199K8711999-01-13013 January 1999 Inservice Insp Rept for Unit 2 Catawba 1998 Refueling Outage 9 ML20247H4141998-04-22022 April 1998 Rev 1 to ISI Rept,Unit 2 Catawba 1997 Refueling Outage 8 ML20217J1691998-03-24024 March 1998 Rev 0 to ISI Rept,Unit 1 Catawba 1997 Refueling Outage 10 ML20199A5341998-01-0404 January 1998 Cns,Unit 2 Class Mc ISI Summary Rept for Refueling Outage EOC9 ML20151J3811997-07-24024 July 1997 to ISI Rept,Unit 2 Catawba 1997 Refueling Outage 8 ML20135D2001996-12-0202 December 1996 Inservice Insp Rept,Unit 1 Catawba 1996 Refueling Outage 9 ML20117F8901996-07-0101 July 1996 Rev 0 to ISI Special Rept for Pressure Testing,Unit 2 Catawba 1996 Refueling Outage 7,Ten Yr Insp Interval ML20100P1511996-02-26026 February 1996 Inservice Insp Rept Unit 2 Catawba 1995 Refueling Outage 7, Rev 0 ML20086F3351995-06-20020 June 1995 Rev 0 to ISI Special Rept for Pressure Testing Unit 1 Catawba 1995 Refueling Outage 8 ML20085F2281995-06-0707 June 1995 Rev 0 to ISI Rept for Unit 1 Catawba 1995 Refueling Outage 8 ML20082A7241995-03-0101 March 1995 Rev 1 to ISI Rept Unit 1 Catawba 1993 Refueling Outage 7 ML20082A7171995-03-0101 March 1995 Rev 1 to ISI Rept Unit 1 Catawba 1992 Refueling Outage 6 ML20073D4501994-09-0808 September 1994 Rev 0 to 1994 ISI Rept for Catawba Nuclear Station,Unit 2, Refueling Outage 6 ML20064N2611994-03-16016 March 1994 ISI Rept Duke Power Co Catawba Nuclear Station Unit 1 Seventh Refueling Outage ML20045C4011993-06-0808 June 1993 Rev 0 to ISI Rept Catawba Nuclear Station,Unit 2,Fifth Refueling Outage. ML20126J5801992-12-21021 December 1992 Rev 0 to ISI Rept,Unit 1 Catawba 1992 Refueling Outage 6 ML20090M8501992-02-26026 February 1992 Rev 0 to Inservice Inspection Rept Catawba Unit 2 1991 Refueling Outage 4 ML20086P5911991-12-18018 December 1991 End-of-Cycle 4 Refueling Outage 15-Day Steam Generator Tube Inservice Insp Rept. Steam Generator Tube Plugging Completed on 911120 ML20083D8221991-09-16016 September 1991 Inservice Insp Rept,Unit 2 Catawba 1990 Refueling Outage 3 ML20077S7431991-08-29029 August 1991 ISI Rept Unit 1 Catawba 1991 Refueling Outage 5 ML20082H8041991-08-21021 August 1991 End-of-Cycle 3 Refueling Outage Steam Generator Insp ML20070L6321991-03-13013 March 1991 Generator Insp Rept Summary, Unit 1 End-of-Cycle 4 Refueling Outage ML20067D0381991-01-28028 January 1991 Rev 1 to ISI Rept Unit 2 Catawba 1990 Refueling Outage 3 ML20062G7221990-11-12012 November 1990 ISI Rept Unit 2 Catawba 1990 Refueling Outage 3 ML20246N4641989-08-15015 August 1989 Rev 1 to Inservice Insp Rept,Unit 2 Catawba 1987 Refueling Outage 1 ML20246L9931989-08-15015 August 1989 Rev 0 to Inservice Insp Rept Unit 2 Catawba 1989 Refueling Outage 2 ML20245A4471989-04-0707 April 1989 Rev 0 to Inservice Insp Rept Unit 1 Catawba 1988 Refueling Outage 3 ML20247A5031989-04-0707 April 1989 Inservice Insp Rept Unit 1 Catawba 1987 Refueling Outage 2 ML20235Z4471989-02-28028 February 1989 Inservice Insp Rept for End of Cycle 1 Refueling Outage Steam Generator ML20150B2601988-02-29029 February 1988 Rev 0 to Inservice Insp Rept,Catawba Unit 1 1987 Refueling Outage 2, Including Final Inservice Insp Plan,Insp Results, Exam Summary,Certification Data for Personnel,Matl & Equipment & Corrective Actions for Unacceptable Conditions ML20210R4481987-01-12012 January 1987 Rev 0 to Inservice Insp Rept,Catawba Unit 1 1986 Refueling Outage 1 1999-08-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9561999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20204C9111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20203A2581999-02-0505 February 1999 Safety Evaluation of TR DPC-NE-3002-A,Rev 2, UFSAR Chapter 15 Sys Transient Analysis Methodology. Rept Acceptable. Staff Requests Duke Energy Corp to Publish Accepted Version of TR within 3 Months of Receipt of SE ML20204C9161999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Catawba Nuclear Station,Units 1 & 2 ML20199K8711999-01-13013 January 1999 Inservice Insp Rept for Unit 2 Catawba 1998 Refueling Outage 9 ML20199E3071998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Catawba Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20205E9441998-12-31031 December 1998 1998 10CFR50.59 Rept for Catawba Nuclear Station,Units 1 & 2, Containing Brief Description of Changes,Tests & Experiments,Including Summary of Ses.With ML20206P2081998-12-31031 December 1998 Special Rept:On 981218,inoperability of Meteorological Monitoring Instrumentation Channels,Was Observed.Caused by Data Logger Overloading Circuit.Replaced & Repaired Temp Signal Processor ML20203A4101998-12-22022 December 1998 Rev 16 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr ML20203A4041998-12-22022 December 1998 Rev 14 to CNEI-0400-24, Catawba Unit 1 Cycle 11 Colr ML20198B1341998-12-14014 December 1998 Revised Special Rept:On 980505,discovered That Certain Fire Barriers Appeared to Be Degraded.Caused by Removal of Firestop Damming Boards.Hourly Fire Watches Established in Affected Areas ML20196J8351998-12-0808 December 1998 Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys ML20199E3221998-11-30030 November 1998 Revised MOR for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20198E3151998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 ML20196C0251998-11-27027 November 1998 SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station ML20196A6881998-11-25025 November 1998 Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds ML20196D4041998-11-19019 November 1998 Rev 1 to Special Rept:On 980618,determined That Method Used to Calibrate Wind Speed Instrumentation Loops of Meteorological Monitoring Instrumentation Sys Does Not Meet TS Definition for Channel Calibration.Procedure Revised ML20195E5521998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20198E3261998-10-31031 October 1998 Revised Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20154M7661998-10-12012 October 1998 LER 98-S01-00:on 980913,terminated Vendor Employee Entered Protected Area.Caused by Computer Interface Malfunction. Security Retained Vendor Employee Badge to Prevent Further Access & Computer Malfunction Was Repaired.With 1999-09-07
[Table view] |
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INSERVICE INSPECTION REPORT UNIT 1 CATAWBA 1993 REFUELING -
OUTAGE 7 Location: 4800 Concord Road, York, South Carolina 29745 n
NATIONAL BOARD. NO.130 Commercial Service Date: June 29,1985 Owner: Duke Power Company 526 S. Church St.
Charlotte, N. C. 28201-1006 Revision 1 l O
1 Prepared By: . .
/IC -
Date 2'2[~ 96 o
Reviewed By: / . Date f-f1- 4 5 Approved By: ,
(t% l4it Date 3 i Q4
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Copy No. 3 Assigned To NRC Document Control Controlled x Uncontrolled
=9504040203 950320 f
.PDR ADOCK 05000413 Q PDR
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.k TABLI ' CONTENTS Section % Revision -
- 1. ~ General Information 0 ;
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- 2. Summary ofInservice Inspections for Outage 7 0 ,
- 3. First Ten Year Interval Inspection Status 1 l
- 4. Final Inservice Inspection Plan for Outage 7 0 ;
- 5. Results ofInspections Performed During Outage 7 0
- 6. Reportable Indications 0
- 7. Personnel, Equipment, and Material Certifications 0 )
- 8. Problem Investigation Process Forms 0
- 9. Rcference Documents 0
( 10. Class 1 and 2 Repairs and Replacements 0 ;
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3.0 First Ten YearIntervalInsnection Status The completion status ofinspections required by the 1980 ASME Section XI l Code, including addenda through Winter 1981,is summarized in this section. ;
The requirements are listed by the ASME Section XI Examination Category as j defined in Table IWB-2500-1 for Class 1 Inspections, and Table IWC-2500-1 ;
for Class 2 Inspections. Augmented inspections are also included. l Class 1 Inspections ,
1 Examination Inspections Inspections Percentage Deferral .
Category Descrintion Reauired Comnleted Comnleted Allowed l B-A Pressure Retaining Welds 14 Welds 14 Welds 100% Yes in Reactor Vessel B-B Pressure Retaining Welds 8 Welds 7 Welds 87.50% No in Vessels Other than Reactor Vessel BD Full Penetration Welds of 36 36 100 % Partial Nozzles in Vessels Inspections Inspections BE Pressure Retaining 55 Welds 55 Welds 67 % No Partial Penetration Welds Credited in Vessels BF Pressure Retaining 46 Welds 46 Welds 100 % No Dissimilar Metal Welds B-G-1 Pressure Retaining 370 Items 366 Items 98.92% Yes l Bolting Greater than 2 Inch Diameter B-G-2 Pressure Retaining 59 52 88.13 % No Bolting 2 Inches and Less Connections Connections in Diameter B-Il Integral Attachment for 12 9 75 % No Vessels Attachments Attachments l
B,1 Pressure Retaining Welds 205 Welds 204 Welds 99.51"4 No in Piping l
Refueling Outage Report Page 1 of 4 l Catawba Unit 1 Revision 1 ;
Section 3 February 27,1995 P
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- 1. . i Jf Q Class 1 Inspections (Continued) 1 Examination . Inspections Inspections Percentage Deferral Category Descrintion Required Completed Completed ' Allowed ;
B-K 1 Integral Attachments for None N/A N/A N/A Piping, Pumps and Valves B L-1 Pressure Retaining Welds None N/A N/A N/A i in Pump Casings B-L-2 Pump Casings None. N/A N/A N/A B-M-1 Pressure Retaining Welds 2 Welds 1 Weld 50% Yes -
in Valve Bodies B-M-2 Valve Body > 4 in. 7 Valves 5 Valves 71.42% Yes ,
Nominal Pipe Size ;
1 B-N 1 Interior of Reactor Vessel 3 Items 3 Items 100 % No l B N-2 Integrally Welded Core None N/A N/A N/A Support Structures and Interior Attachments to ,
I- Reactor Vessels I b Removable Core Support 1 Item Yes B-N 3 1 Item 100%
Structures B-0 Pressure Retaining Welds 3 Housings 3 Housings 100% Yes in Control Rod Housings BP All Pressure Retaining Components System Leakage Test 140 140 100% .No Components Components System Hydrostatic Test 20 0 0% Yes Components Components B-Q Steam Generator Tubing As stated in 100% Station 100% Station No Station Technical Technical Technical Specifications Specifications Specifications Met Met -
F1.01 Class 1 Component 267 Supports 265 Supports 99.25 % No Supports O Refueling Outage Report Page 2 of 4 Revision 1 l
Catawba Unit 1 Section 3 February 27,1995
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V Class 2 Inspections 1
Examination Inspections Inspections . Percentage Deferral Catecorv . Descriotion Reanired Completed Completed - Allowed C.A Pressure Retaining Welds 9 Welds 7 Welds 77.77% - No.
in Pressure Vessels CB Pressure Retaining Nozzle - 6 Welds 6 Welds 100% No Welds in Vessels C-C Integral Attachments for 33 27 81.81% No
. Vessels, Piping, Pumps Attachments Attachments and Valves C-D Pressure Retaining None N/A N/A N/A Bolting Exceeding 2 Inches in Diameter CF Pressure Retaining Welds 347 Welds 327 Welds 94.23 % No in Piping CG Pressure Retaining Welds 25 Welds 15 Welds 60% Yes in Pumps and Valves tO C.Il All Pressure Retaining Components System or Component 70 @ 98.57% No Functional Test Components Components System Hydrostatic Test 90 'll 30% Yes Components Components F1.02 Class 2 Component 552 Supports 551 Supports 99.81% No Supports b
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Refueling Outage Report Page 3 of 4 l Catawba Unit 1 Revision 1 Section 3 February 27,1995 I
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Augmented Inspections Descrintion Percentage Comoleig - !
Reactor Coolant Pump Flywheels 100% of Technical Specifications met ,
Steam Generator Tubes on Preheater Section 100% of requirements met for Outages 1,2,3,4, 5,6, & 7 ;
Main Steam Pipe Rupture Protection 100% of requirements met for Outages 1,2,3,4, 5,6, & 7 .
Class 2 Piping Systems 100% of requirements met for Outages 1,2,3,4, 5,6, & 7 Thermal Stress Piping (NRC Bulletin 88-08) 100% of requirements met for Outages 3 & 6 Safety injection Accumulator Nozzles (NRC 100% of requirements met for Outage 5 Information Notice 91-05) i
+ ],
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1 Deferral on inspection to the end of the interval as allowed by ASME Section XI Tables IWB and l I
IWC-2500 '
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% Refueling Outage Report Page 4 of 4 l Catawba Unit 1 Revision 1 Section 3 February 27,1995
t
. 371 Pages t
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FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTION S As required by the Provisions of the ASME Code Rules
- 1. Owner: Duke Power Company 526 S. Church St.. Charlotte. NC 28201-1006 (Nameand Address of Owner)
- 2. Plant: Catawba Nuclear Station 4800 Concord Road York SC 29745 (Name and Address of Plant)
- 3. Plant Unit: 1 4. Owner Certificate of Authorization (if required) N/A
- 5. Commercial Service Date: 6/29/85 6. National Board Number for Unit DD
- 7. Components inspected:
Component or Manufacturer or Manufacturer or State or National Appurentance Installer Installer Serial Providence No. Board No.
No.
See Section 1 Paragraph 1.1 in the Attached Report V .-
Nine:
I Nupplemental sheete in fem of hats. sketches. or d rewings may be uwd proyuled (1) sue is 8 2/ in. a 11 in,(2)Informanon in nerns 1 thrnugh 6 on this data repost is included on each sheet, and (1) each sheet is nurrtered and the nuenher d sheets to recorded at the top of thm farm l
I l
lO Q \
This NIS-1 Form supersedes the previous NIS-1 Form submitted with Rev.0 of this report .
[
- . :s - ;
,- 371 PageS ,
i
,,-q:
/ ) ' FORM NIS-1(backl l v
/- ,
8.' Examination Dates 10/15/92 to 12/27/93 Inspection Interval from 06/29/85 to 06/29/95
- 10. - Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. See attached reoort.
- 11. Abstract of Conditions Noted. Sgg. attached report.
- 12. Abstract of Corrective Measures Recommended and Taken. See attached ret; ort.
We certify that the statements made in this report are correct and the examinations and corrective ,
measures taken conform to the rules of the ASME Code,Section XI Date 3 i 19.9c; Signed Duke Power Co. By _
O '
Owner Certificate of Aethorization No.(if applicable) N/_A Expiration Date N/A
\
l CERTIFICATE OF INSERVICE INSPECTION l l
I, the undersigned, holding a valid commission inued by the National Board of Boiler and Pressure Venel Inspectors and/or the State or Province of .
and employed by l
- The HSBl&1 Co. of have inspected the components described in this Owners ;
\ Data Report during the period i O - / $ N to / 2 2 Mand state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed j 1
or implied,concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or loss of any kind arising from or connected with this inspection.
Date 3 I 19 ) b N Y)M ' ik UI Commissions
}
' \ nspector's i Signature National Board, State, Province and No.
"The Hartford Steam Ik>iler inspection & Insurance Co. i 200 Ashford Center North Suite 300 Atlanta Ca. 30338 This NIS-1 Form supersedes the previous NIS 1 Form submitted with Rev. 0 of this report